APPLICATION OF CODE SCALING, APPLICABILITY AND UNCERTAINTY METHODOLOGY TO LARGE BREAK LOCA ANALYSIS OF 2 LOOP PWR

In NED 119, No. 1 (May 1990) a series of six papers published by a Tec hnical Program Group presented a new methodology for the safety evalua tion of emergency core cooling systems in nuclear power plants. This p aper describes the application of that new methodology to the LB LOCA analysis of the two loop Westinghouse power plant. Results of the orig inal work were used wherever possible, so that the analysis was finish ed in less than one man year of work. Steam generator plugging level a nd safety injection flow rate were used as additional uncertainty para meters, which had not been used in the original work. The computer cod e RELAP5/MOD2 was used. Response surface was generated by the regressi on analysis and by the artificial neural network like Optimal Statisti cal Estimator method. Results were compared also to the analytical cal culation.